05000482/FIN-2013008-08
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Finding | |
|---|---|
| Title | Failure to Account for Containment Temperature Measurement Uncertainty |
| Description | The team identified a Green, non-cited violation of 10 CFR 50, Appendix B, Criterion III, Design Control, which states, in part, Measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions. The design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program. Specifically, on August 28, 2013, the team identified that the licensee had failed to have adequate controls in place to ensure that the bulk average containment temperature would not exceed the Technical Specification limit and design basis limit of 120F. The licensee did not have: 1) a calculation addressing containment temperature indication uncertainty, 2) there was a lack of temperature sensor and associated circuitry uncertainty, 3) and there was no calculation or justification addressing potential temperature stratification in containment. The licensee has entered these issues into their corrective action program as Condition Reports CR-72639, CR-73118, and CR-73152. The team determined that the failure to account for instrument uncertainty on the containment bulk average temperature instrumentation used to determine containment operability was a performance deficiency. This finding was more than minor because it was associated with the Design Control attribute of the Reactor Safety, Barrier Integrity Cornerstone, and adversely affected the cornerstone objective to ensure that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, by not accounting for the temperature measurement accuracy and stratification, the containment temperature could unknowingly exceed the Technical Specification operability limit. In accordance with NRC Inspection Manual Chapter 0609, Appendix A, Exhibit 3, Barrier Integrity Screening Questions, the finding was determined to have a very low safety significance (Green), because it did not result in an actual open pathway in containment and did not involve hydrogen igniters. Operability Evaluation OE GN-13-006 evaluated the containment temperature concerns and concluded that the containment would be operable, but degraded or nonconforming. This finding did not have a cross-cutting aspect because the most significant contributor to the performance deficiency did not reflect current licensee performance. |
| Site: | Wolf Creek  |
|---|---|
| Report | IR 05000482/2013008 Section 1R21 |
| Date counted | Sep 30, 2013 (2013Q3) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.21 |
| Inspectors (proximate) | S Garchow B Correll A Sengupta H Leake R Kopriva T Farnholtz |
| Violation of: | Technical Specification - Procedures 10 CFR 50 Appendix B Criterion III, Design Control Technical Specification |
| INPO aspect | |
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Finding - Wolf Creek - IR 05000482/2013008 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Wolf Creek) @ 2013Q3
Self-Identified List (Wolf Creek)
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